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| FUNDAMENTALS OF NUCLEAR REACTOR PHYSICS
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To order this title, and for more information, click here
By
Elmer Lewis, Ph.D., Northwestern University, Department Of Mechanical Engineering, Robert R. McCormick School of Eng. & Applied Science, Evanston, IL, USA
Description
This new streamlined text offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches
to the design of reactors, and their safe and efficient operation. The book includes numerous worked-out examples and end-of-chapter
questions to help reinforce the knowledge presented.
This textbook offers an engineering-oriented introduction to nuclear physics,
with a particular focus on how those physics are put to work in the service of generating nuclear-based power, particularly the importance
of neutron reactions and neutron behavior. Engineering students will find this applications-oriented approach, with many worked-out examples,
more accessible and more meaningful as they aspire to become future nuclear engineers.
Audience
Junior and Senior Undergraduate engineering students in mechanical, nuclear, and materials engineering , Junior and Senior Undergraduate
students in physics, Graduate Students in other engineering disciplines in need of an introductory text, including those in Electrical
engineering and Environmental and Health and Safety engineering, Professional Engineers in Mechanical, Nuclear and Materials Engineering,
Managers and Technicians in the power-generation industries, Administrators charged with regulatory and safety issues affecting the nuclear
power industry
Contents
1. Nuclear Reactions
1.1 Introduction
1.2 Nuclear Reaction Fundamentals
1.3 The Curve of Binding Energy
1.4 Fusion Reactions
1.5 Fission
Reactions
1.6 Fissile and Fertile Materials
1.7 Radioactive Decay
2. Neutron Interactions
2.1 Introduction
2.2 Neutron Cross Sections
2.3 Neutron Energy Range
2.4 Cross Section Energy Dependence
2.5 Neutron Scattering
3. Neutron Distributions in Energy
3.1 Introduction
3.2 Nuclear Fuel Properties
3.3 Neutron Moderators
3.4 Neutron Energy Spectra
3.5 Energy-Averaged Reaction Rates
3.6 Infinite Medium
Multiplication:
4. The Power Reactor Core
4.1 Introduction
4.2 Core Composition
4.3 Fast Reactor Lattices
4.4 Thermal Reactor Lattices
5. Reactor Kinetics
5.1 Introduction
5.2 Neutron Balance Equations
5.3 Multiplying Systems Behavior
5.4 Delayed Neutron Kinetics
5.5
Step Reactivity Changes
5.6 Prolog to Reactor Dynamics
6. Spatial Diffusion of Neutrons
6.1 Introduction
6.2 The Neutron Diffusion Equation
6.3 Non-multiplying Systems- Plane Geometry
6.4 Boundary Conditions
6.5 Non-multiplying Systems- Spherical Geometry
6.6 Diffusion Approximation
Validity
6.7 Multiplying Systems
7. Neutron Distributions in Reactors
7.1 Introduction
7.2 The Time-Independent Diffusion Equation
7.3 Uniform Reactors
7.4 Neutron Leakage
7.5 Reflected Reactors
7.6 Control Poisons
8. Energy Transport
8.1 Introduction
8.2 Core Power
Distribution
8.3 Heat Transport
8.4 Thermal Transients
9. Reactivity Feedback
9.1 Introduction
9.2 Reactivity Coefficients
9.3 Composite
Coefficients
9.4 Excess Reactivity and Shutdown Margin
9.5 Reactor Transients
10. Long Term Core Behavior
10.1 Introduction
10.2 Reactivity
Control
10.3 Fission Product Buildup and Decay
10.4 Fuel Depletion
10.5 Fission Product and Actinides Inventories
Appendices
A. Useful
Mathematics
B. Bessel's Equation and Functions
C. Derivation of Neutron Diffusion Properties
D. Fuel Element Heat Transfer
E. Nuclear
Data
| Bibliographic details |
Hardbound, 280 pages, publication date: JAN-2008
ISBN-13: 978-0-12-370631-7
ISBN-10: 0-12-370631-9
Imprint: ACADEMIC PRESS
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| Price and Ordering |
Price:
GBP 59.99
USD 99.95
EUR 70.95
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Last update: 25 Nov 2009
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